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Chinese Academy of Sciences Institutional Repositories Grid
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CAS IR Grid
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金属研究所 [5]
宁波材料技术与工程研... [2]
近代物理研究所 [2]
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OAI收割 [10]
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期刊论文 [10]
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2025 [2]
2023 [1]
2021 [5]
2019 [1]
2018 [1]
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Effects of coolant pH on crud deposition behavior on fuel cladding tube under subcooled nucleate boiling condition in high temperature pressurized water
期刊论文
OAI收割
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 603, 页码: 13
作者:
Lin, Zihao
;
Zhang, Ziyu
;
Tan, Jibo
;
Wu, Xinqiang
  |  
收藏
  |  
浏览/下载:1/0
  |  
提交时间:2025/04/27
Crud deposition
Fuel cladding tube
Coolant pH
Subcooled nucleate boiling
Solubility
Effects of coolant pH on crud deposition behavior on fuel cladding tube under subcooled nucleate boiling condition in high temperature pressurized water
期刊论文
OAI收割
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 603, 页码: 13
作者:
Lin, Zihao
;
Zhang, Ziyu
  |  
收藏
  |  
浏览/下载:2/0
  |  
提交时间:2025/04/27
Crud deposition
Fuel cladding tube
Coolant pH
Subcooled nucleate boiling
Solubility
Effects of Zn injection on corrosion behavior and crud deposition of FeCrAl fuel cladding under subcooled nuclear boiling condition in high-temperature pressurized water
期刊论文
OAI收割
CORROSION SCIENCE, 2023, 卷号: 211, 页码: 16
作者:
Xue, Chaochao
;
Zhang, Ziyu
;
Tan, Jibo
;
Wu, Xinqiang
;
Han, En-Hou
  |  
收藏
  |  
浏览/下载:57/0
  |  
提交时间:2023/05/09
FeCrAl fuel cladding
Corrosion behavior
Crud deposition
Zn injection
Subcooled nuclear boiling
Irradiation behaviors of two novel single-phase bcc-structure high-entropy alloys for accident-tolerant fuel cladding
期刊论文
OAI收割
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2021, 卷号: 84, 页码: 230-238
作者:
Zhang, Zijian
;
Han, En-Hou
;
Xiang, Chao
  |  
收藏
  |  
浏览/下载:82/0
  |  
提交时间:2021/10/15
High-entropy alloy
Accident-tolerant fuel cladding
Helium-ion irradiation
Microstructure
Irradiation hardening
In situ transmission electron microscopy study and molecular dynamics simulation of dislocation loop evolution in FeCrAl alloys under Fe+ irradiation
期刊论文
OAI收割
MATERIALS TODAY ENERGY, 2021, 卷号: 21, 页码: 12
作者:
Li, Y. P.
;
Yu, M. S.
;
Ran, G.
;
Gao, N.
;
Chen, Y.
  |  
收藏
  |  
浏览/下载:61/0
  |  
提交时间:2021/12/08
In situ TEM observation
Loop reaction
Molecular dynamics simulation
Fuel cladding
Irradiation damage
Effects of ion irradiation on Cr, CrN, and TiAlCrN coated Zircaloy-4 for accident tolerant fuel claddings
期刊论文
OAI收割
ANNALS OF NUCLEAR ENERGY, 2021, 卷号: 156, 页码: 9
作者:
Song Ligang
;
Huang Bo
;
Li JH(李江华)
;
Ma Xianfeng
;
Liu Min
  |  
收藏
  |  
浏览/下载:74/0
  |  
提交时间:2021/05/17
Accident tolerant fuel
Cladding coatings
Zircaloy-4
Au ion irradiation
Grain boundary
A damage-effect-involved phenomenological crystal plasticity model and computational methods for mechanical responses of FeCrAl alloys
期刊论文
OAI收割
MATERIALS TODAY COMMUNICATIONS, 2021, 卷号: 28
作者:
Zhang, Jingyu
;
Ding, Shurong
;
Du, Shiyu
  |  
收藏
  |  
浏览/下载:42/0
  |  
提交时间:2021/12/01
NEUTRON-IRRADIATED MODEL
TOLERANT FUEL SYSTEM
ORIENTATION DEPENDENCE
ANISOTROPIC DAMAGE
CLADDING MATERIALS
STAINLESS-STEEL
BCC IRON
DEFORMATION
BEHAVIOR
MICROSTRUCTURE
A damage-effect-involved phenomenological crystal plasticity model and computational methods for mechanical responses of FeCrAl alloys
期刊论文
OAI收割
MATERIALS TODAY COMMUNICATIONS, 2021, 卷号: 28
作者:
Zhang, Jingyu
;
Ding, Shurong
;
Du, Shiyu
  |  
收藏
  |  
浏览/下载:59/0
  |  
提交时间:2021/12/01
NEUTRON-IRRADIATED MODEL
TOLERANT FUEL SYSTEM
ORIENTATION DEPENDENCE
ANISOTROPIC DAMAGE
CLADDING MATERIALS
STAINLESS-STEEL
BCC IRON
DEFORMATION
BEHAVIOR
MICROSTRUCTURE
Effect of aluminum content on dislocation loops in model FeCrAl alloys
期刊论文
OAI收割
NUCLEAR MATERIALS AND ENERGY, 2019, 卷号: 21, 页码: 7
作者:
Zhou, Xiong
;
Guo, Liping
;
Wei, Yaxia
;
Wang, Hui
;
Chen, Cheng
  |  
收藏
  |  
浏览/下载:50/0
  |  
提交时间:2021/02/02
FeCrAl alloy
Dislocation loops
Radiation damage
Accident tolerant fuel cladding
Microstructural evolution of epitaxial Ti3AlC2 film on sapphire under ion irradiation and nanoindentation-induced deformation
期刊论文
OAI收割
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 509, 页码: 181-187
作者:
Huang, Qing
;
Wang, Ji
;
Shao, Tao
;
Ren, Donglou
;
Liu, Shaoshuai
  |  
收藏
  |  
浏览/下载:70/0
  |  
提交时间:2018/10/08
Ion irradiation
Accident tolerant fuels
Fuel cladding coating
Ti3AlC2
MAX phase film